A study on the impact of using a subchannel resolution for modeling of large break loss of coolant accidents

R Salko, A Wysocki, B Hizoum, N Capps - Annals of Nuclear Energy, 2024 - Elsevier
The nuclear industry is investigating the feasibility of transitioning from 18-to 24-month fuel
cycles because of the positive impact it would have on the operational costs for the current …

Assessment of the CTF subchannel code for modeling a large-break loss-of-coolant accident reflood transient

R Salko, A Wysocki, B Hizoum, N Capps - Annals of Nuclear Energy, 2025 - Elsevier
With increased industry interest in extending reactor operating cycles, the neams!(neams!)
program has been investigating the behavior of high-burnup fuel during design basis …

Impact of LWR assembly structural features on cladding burst behavior under LOCA conditions

D Schappel, N Capps - Nuclear Engineering and Design, 2024 - Elsevier
This provides an initial sco** study on clad balloon and burst behavior for burnup
extension of reactor fuel. The associated issues with burnup extension are fuel …

A realistic TRACE PWR LOCA model with application to high-burnup analysis

A Wysocki, N Capps - Annals of Nuclear Energy, 2025 - Elsevier
This paper presents a TRACE model of a postulated large-break loss-of-coolant accident
(LBLOCA) event in a four-loop pressurized water reactor (PWR). The input files have been …

Comparison between Pin-by-Pin Subchannel and System Level Thermal Hydraulic Results for High Burnup Loss-of-Coolant Applications

R Salko Jr, A Wysocki, B Hizoum, N Capps - 2023 - osti.gov
This milestone report summarizes recent work to investigate higher fidelity modeling and
simulation practices for large-break loss-of-coolant accident (LBLOCA) analysis in high …

Effects of transient fission gas release on rod balloon burst behavior during a loss-of-coolant accident

I Greenquist, N Capps - Annals of Nuclear Energy, 2024 - Elsevier
The US nuclear energy industry is investigating strategies to increase the reactor operating
cycle to 24 months, which would result in rod average burnups exceeding the current limit of …

[PDF][PDF] High-Burnup BWR LOCA Burst Analysis Framework Development and Demonstration

N Capps, M Asgari, A Wysocki, I Greenquist… - 2024 - osti.gov
In the United States, boiling water reactors (BWRs) comprise approximately one-third of the
fleet, although much of the research and development focus has traditionally been on …